tailieunhanh - Numerical evaluation of gamma radiation monitoring

In this study a new AGRS system empowered by ANN-BFGS has been proposed and evaluated on available empirical AGRS data. To that effect different architectures of adaptive ANN-BFGS were implemented for a sort of published experimental AGRS outputs. The selected approach among of various training methods, with its low iteration cost and nondiagonal scaling allocation is a new powerful algorithm for AGRS data due to its inherent stochastic properties. | Nuclear Engineering and Technology 51 2019 807 817 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage locate net Original Article Numerical evaluation of gamma radiation monitoring Mohsen Rezaei Mansour Ashoor Leila Sarkhosh Nuclear Science and Technology Research Institute AEOI Tehran 1439955931 Iran ARTICLE INFO ABSTRACT Article history Received 21 July 2018 Received in revised form 14 November 2018 Accepted 24 December 2018 Available online 25 December 2018 Keywords Artificial neural networks BFGS training algorithm Airborne gamma ray spectrometry Nuclear site surveillance Airborne Gamma Ray Spectrometry AGRS with its important applications such as gathering radiation information of ground surface geochemistry measuring of the abundance of Potassium Thorium and Uranium in outer earth layer environmental and nuclear site surveillance has a key role in the field of nuclear science and human life. The Broyden Fletcher Goldfarb Shanno BFGS with its advanced numerical unconstrained nonlinear optimization in collaboration with Artificial Neural Networks ANNs provides a noteworthy opportunity for modern AGRS. In this study a new AGRS system empowered by ANN-BFGS has been proposed and evaluated on available empirical AGRS data. To that effect different architectures of adaptive ANN-BFGS were implemented for a sort of published experimental AGRS outputs. The selected approach among of various training methods with its low iteration cost and nondiagonal scaling allocation is a new powerful algorithm for AGRS data due to its inherent stochastic properties. Experiments were performed by different architectures and trainings the selected scheme achieved the smallest number of epochs the minimum Mean Square Error MSE and the maximum performance in compare with different types of optimization strategies and algorithms. The proposed method is capable to be implemented on a cost effective and minimum electronic .

• Năng lượng
• Nuclear engineering and technology
• Numerical evaluation of gamma radiation monitoring
• Gamma radiation monitoring
• Inherent stochastic properties
• BFGS training algorithm
• Airborne gamma ray spectrometry
• Nuclear site surveillance
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
• Economic Co operation and Development
• Nuclear Energy Agency
• Nuclear Criticality Safety
• Expanded spent fuel isotopic compositions
• Nuclear reactor vessel water level prediction during severe accidents
• Deep neural networks
• Nuclear power plants
• Maintain nuclear reactor integrity
• Special issue on the International Symposium
• Future Instrumentation and Control for Nuclear Power Plants
• The Nuclear Engineering and Technolog
• Parameter identifiability of Boolean networks
• Application to fault diagnosis of nuclear plants
• Fault diagnosis of nuclear plants
• Nuclear Heating Reactor
• Sensor selection strategy
• Radioactive effluents released from Korean nuclear power plants
• The resulting radiation doses to members of the public
• Korean nuclear power plants
• Nuclear power plant
• The recycling of nuclear graphite after micro oxidation
• Nuclear graphite after micro oxidation
• Whether ground micro oxidation graphite
• The oxidized graphite particles
• The recycling of nuclear graphite
• Statistical model for forecasting uranium prices
• Estimate the nuclear fuel cycle cost
• Nuclear Fuel Cycle Cost
• Nuclear fuel cycle cost calculation
• The statistical autoregressive integrated moving average
• Distinct properties of tungsten austenitic stainless alloy
• Potential nuclear engineering material
• Interchanging the molybdenum in standard SS316 by tungsten
• Gamma and neutron shielding Interchanging the molybdenum
• Nuclear engineering and design
• Brayton cycle
• Supercritical carbon dioxide
• Nuclear engineering
• Safety analysis
• Control strategy
• Seismic fragility evaluation
• The base isolated nuclear power plant piping system
• The failure criterion based on stress strain
• Nuclear power plant piping system
• Seismic fragility analysis
• BNL NRC benchmark model
• Feasibility study on photo production
• 99mTc with the nuclear resonance fluorescence
• The nuclear resonance fluorescence
• High intensity laser Compton scattering
• Improved PCA method
• Sensor fault detection and isolation in a nuclear power plant
• Sensor fault detection and isolation
• Influences of heating processes on properties
• Microstructure of porous CeO2 beads
• Surrogate for nuclear fuels fabricated
• Microfluidic sol gel process
• The ceramic nuclear fuel particles
• Sensitivity analysis of thermal hydraulic parameters
• The corrosion intensity in nuclear power plant steam generators
• Nuclear power plant steam generators
• The failure of steam generators
• The heat exchangers
• Architectural model driven dependability analysis
• Computer based safety system in nuclear power plant
• Safety system in nuclear power plant
• Embedded Real Time Safety Systems
• Mitigation of high energy arcing faults
• Nuclear power plant medium voltage switchgear
• High energy arcing fault
• Ultra high performance fiber reinforced concrete nuclear waste container
• High level waste
• Ultra high performance fiber reinforced concrete material
• The dry storage container
• Canadian Nuclear facilities
• Real time estimation of break sizes during LOCA
• Nuclear power plants using NARX neural network
• Nonlinear autoregressive with exogenous inputs
• Loss of coolant accidents
• Nordic research and development cooperation
• Strengthen nuclear reactor safety after the Fukushima accident
• The Fukushima accident
• Nordic Nuclear Safety Research
• Seismic response characteristics
• Isolated AP1000 nuclear shield building subjected
• Beyond design basis earthquake shaking
• Beyond Design Basis Earthquake
• Nuclear Shield Building
• Uncertainty analysis of containment dose rate
• Containment dose rate for core damage assessment
• Containment Radiation Monitor
• Core Damage Assessment
• An evaluation method for nuclear fuel debrisefiltering performance
• Nuclear fuel debrisefiltering performance
• Comprehensive Debris Filtering Efficiency
• Debris Filtering Performance
• Debris Induced Failure
• Development of earthquake instrumentation for shutdown
• Restart criteria of the nuclear power plant
• Multivariable decision making process
• The nuclear power plant
• Development of an information reference system
• Reconstruction models of nuclear power plants
• Work site reconstruction models
• Six nuclear power plant workers
• Nondestructive inspection of spent nuclear fuel storage canisters
• Shear horizontal guided waves
• Spent nuclear fuel storage canisters
• The cask protecting the canister
• Geometric constrains inside